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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
[Table view] |
Text
._.
w-Submitted: _ SP humber 29.023.03 (Section Head)
Approved: Revicion C (Plant Manager)
Effettive Date
~
REACTOR PRESSURE VESSEL FLOODING EMERGENCY PROCEDURE f.1E . E 1.0 PUPSOSE MEUlh,.=Ha f3:.i e
5 7
i The purpose of this procedure is tes flood the RPV using all the available injection subsystems.
2.0 ENTRY CONDITIONS This procedure is entered from SP 29.023.05 (Rapid RPV Depressurization) if any of the following occur:
2.1 Temperature near the cold reference leg instrument vertical runc exceeds the RPV saturation limit.
2.2 RPV water level cannot be determined.
2.3 Suppression chamber pressure er.ceeding cuppression limit.
3.0 OPERATOR ACTIONS 3.1 If at least (later) SRV's are open, or if core cpray or other motor driven feedwater pumps are availr.ble for injection, perform the following.
3.1.1 All MSIV's 1B21-A0V-081A ~
IS21-A0V-082A 1B21-A07-081B IB21-A0V-082B 1B21-A0V-001C ~ IB21-A0V-082C IB21-A0V-081D 1B21-A0V-082D 3.1.2 MSL Drain Lines IB1 MGV-038 IB21 MOV-033 IB1.. A0V-088 IB21 A0V-089 i _
I 3.1.3 RHR Steam Condensing Valve _
1El1 MOV-049 3.1.4 HPCI Isolation Valves IE41 MOV-041 1E41 MOV-047 1E41 MOV-042 IE41 MOV-048 g= ,i ! . et .o i
/ G % sm s-8107230268 810720- ?h f PDR ADOCK 05000322 A _
3.1.5 -RCIC leciatica Vilv:s s
1E51 MOV-041 1E51 MOV-047
-1E51 MOV-042 1E51 MOV-048 3.1. 6 - RWCU Isolation Valves 1G33*MOV-031 IG33*MOV-041 1G33*MOV-032-3.2 ' Inject water into the RPV with all of the following.
3.2.11 Core spray per SP 23.204.01 Core Spray System.
3.2.2 condensate booster pumps per SP 23.103.01 Condensate.
3.2.3 _LPCI per SP- 23.204.01 Low Pressure Coolant Injection.
3.2.4 Condensate pumps per SP 23,103.01 Condensate.
3.2.5' 'CRD'per SP 23.106.01 Control Rod Drive.
3.3._ If.RPV water level is' increasing, then continue in this procedure
.at Step 3.7.
3.4 L When RPV pressure is stable,' cycle one SRV closed for about 3 minutes and then open to determine the single SRV pressure rise.
3.5 :1f the single SRV pressure rise exceeds the minimum single SRV 1 pressure rise,' Fig.11, continue in this procedure at paragraph 3.7. If the single SRV pressure rise is less than the minimum single SRV pressure rise, per form Step 3.6.
3.6 Inject. water'into the RPV with all of the following.
[~ 3.6.1 Service water /recirc loop ultimate cooling water crosstie-valves IP41-MOV-033A, MOV-933B, MOV-933C and MOV-033D.
3.6.2- ECCS connections from the condensate transfer system.
l 3.6.3 SLC .(test tank) and SLC (boron tank) per SP 23.123.01.
_ 3. 7_ LIf-suppression chamber pressure cannot be maintained below the primary containment pressure limit, Fig. 2, initiate the following systems irrespective of whether adequate core cooliPS is assured:
3.7.1 Drywell sprays 3.7.2 Suppression pool sprays only when suppression pool water level is below (later)
' ' SP29.923.99 Rev. C
/ / Page 2 L'
w en-m- -,-c,we,,- -
CAUTION Defeating' isolation interlocks may be required to acconplish this step.-
5.8. If suppression chamber pressure exceeds the primary containment
. pressure limit, vent the primary containment in accordance with
_(later) to reduce pressure below the primary containment pressure
-limit.
3.9 Fill all RPV level instrumentation reference columns. _.
3.10 Continue injection until temperature near the cold refercnce leg
- vertical runs is below 212*F and RPV water level instrumentation is available.
3.11 If it can be determined that the RPV is filled, continue in this procedure at step 3.14.
~ NOTE: Several methods of determining if the RPV is filled are provided, however, these may not be the only means.
.c.
3.11.1 RPV water level indication ,
~3.11.2 Starting and stopping a condensate booster pump and determining that the pressure in the vessel goes to the shutoff head of the booster pump.
3.11.3 If no external source is being injected a stable RPV
. pressure coincident with a stable suppression pool level
-may indicate the RPV filled.
~
3.11.4 ' A rapid increase in suppression pool temperature may -
indicate the RPV filled.
3.11.5 The open SRV's tailpipe temperature increasing to and equalizing with RPV temperature may indicate the RPV filled.
3.12 If the level is still unknown, cycle one SRV closed for above three minutes and back open to determine the RPV pressure rise (referred to as single SRV pressure rise). If the RPV pressure indicates the vessel is filled, proceed to step 3.14.
3.13. If the single SRV pressure rise is less than the minimum single SRV pressure rise, return to paragraph 3.11.
SP29 923 99 Rev. C
/ / Page 3
' CAUILON Refer to Figure 3 for maximum acceptance core uncovery time prior to performance of step 3.14.
3.14 Terminate all injection into the RPV and reduce RPV water level.
3.15 -1f RPV water level indication is not restored within the maximum acceptable core uncovery time as determined by Figure 3, return to paragraph 3.2.
3.16 .lf RPV water level indication is restored within the maximum acceptable core uncovery time as' determined in paragraph 3.15, proceed to SP 29.923 91 (level control) at paragraph 3.3.
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